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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
T. D. Bohm, M. E. Sawan, P. Wilson
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 731-735
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST09-A8995
Articles are hosted by Taylor and Francis Online.
Gaps exist between the first wall/shield (FWS) modules of ITER to allow for fitting by remote handling equipment. Simplified three-dimensional models were used at the top and mid-plane locations to analyze gap streaming. Heating, helium production, and fast neutron fluence were examined at the front of the vacuum vessel and the magnet for both straight and stepped gaps. In addition, total nuclear heating values in the inboard magnet and central solenoid were examined for straight and stepped vertical gaps and for combined horizontal and vertical straight gaps. The results show significant radiation streaming effects that are more pronounced for fast neutron fluence and helium production. Furthermore, it was found that stepping the gap significantly reduces the local peaking, but has little effect on the relative average values of radiation effects. The results also show increases up to 75% in total magnet heating at the inboard mid-plane location for a straight 2 cm combined vertical and horizontal gap.